[2A04-07] Irradiation Behavior of Fuel Pellets and Claddings

[2A07] Effect of fabrication condition on irradiation growth of Zircaloy-4 cladding tube

*Kazuo Kakiuchi¹, Masaki Amaya¹ (1. JAEA)

Keywords:PWR, Zircaloy-4, Cladding tube, Irradiation growth, fabrication condition

The irradiation growth test for various type of improved Zr alloy had been performed in Norway Halden reactor in order to understand the dimension stability for long-term usage of PWR fuel as a technical program sponsored by Nuclear Regulation Authority, Japan. Firstable, it reports the influence on the final heat treatment (Cold-Worked material, Stress-Relieved material and Recrystallized material) in the fabrication process and Q-value which shows indication of the rolling ratio for the conventional Zircaloy-4 cladding tube. Regarding the irradiation growth rate, Recrystallized material showed the smaller tendency compared with Cold-Worked material and Stress-Relieved material. And also, it tended to accelerate at first neutron fluence of 5E+25 (1/m², E>1MeV). On the other hand, the influence on Q-value was not significant.